ML080170543

Summary of December 12, 2007, Meeting with Tennessee Valley Authority on Reconstruction of the Licensing Basis for Watts Bar Unit 2

ML080170543
Person / Time
Site:	Watts Bar
Issue date:	01/03/2008
From:	Chernoff M Plant Licensing Branch III-2
To:
Chernoff M, NRR/DORL, 415-4041
Shared Package
ML073520705	List: ML073520971 ML080170543
References
TAC MD6311
Download: ML080170543 (12)

Text

WATTS BAR NUCLEAR PLANT UNIT 2 Regulatory Framework Overview December 12,-2007 ENCLOSURE 2

Regulatory Framework - Development Logic No S No Additonal ValidLinen.. ACOl, Ba...

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No Renornoneoda. ValidUnit Roforeno. 2 Uinen. Seia Y- Changedý... R N 5056 Proooe RatDiem,1ftoned cio Ye.

A.ke*dtblt oNRCee No B.d.edtaNflC.-

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Unit2 No Deodof,

-- Alternate .iIBe'taBmClII

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, on AAR~ooit, S.-n.. U UIt G. Arent 4

Regulatory Framework - Development &

Closure Logic lio INPUT Yes roposed Action(s) Yes u Construction ., Validate Corrective Remains Valid for Deficiency Reports Action Completed u Inspection Items Unit 2?

• Commitments u Corrective Action Program (CAPs) No U Special Programs U CAQRs No u Employee Concerns

, New Generic Communications Q Generic Safety Issues U Margin supporting Dual Unit Operation U. U1 Issues U LERs

, 10CFR50.59s U Inspection Items Yes Confirm/Determine Action Yes Validate Corrective Closure to Resolve for Action Completed Package A

No Yes No No ZNRCApproval Received?

Yes No al .Yes

. . .... I- NRC to Submit Y Perform Unit 1 Action No on Unit 2?

Yes G. Arent 5.

Regulatory Framework - Example 1* 119 Approved Unit Two Licensing Basis 1982 SER SRP TITLE Approval for WBN Approval Guidance Additional Information Unit 2 Reference (GL, Bulletins, other) 3.9.5 3.9.5 - Reactor Pressure Original 1982 SER

__ _ Vessel Internals

• Draft Information for Illustration Only G. Arent 6

Regulatory Framework - Example _2* IM Approved Unit One Licensing Basis - Same Approach for Unit Two 1982 SER SRP TITLE Approval for WBN Approval Guidance Additional Information Unit 2 Reference (GL, Bulletins, other)

Note I 3.7.3 3.7.3 - Seismic Subsystem 3.7.3-Outstanding issue Code case use, The staff reviewed the list of specific ASME Code Analysis involving use of code damping factors cases TVA intended to use and found that they cases, damping factors for conduit were either incorporated into the ASME Code or for conduit and use of SSER8 - endorsed in Position C. 1-of RG 1.84. This issue worst case, critical case January 1992, was considered resolved in SSER8.

and bounding case use of worst case, critical Deficiencies identified in the use of worst case, case and critical case and bounding calculations were bounding resolved in IR 50-390/93-201 and this issue was calculations for considered resolved for Unit 1 in SSER12.

Unit 1 only in SSER12 - . *ConduitSupports Corrective Action Program.*

October 1993 Process was reviewed and determined to be (CAP/SP acceptable for Unit I in SER dated September 1, implementation 1989. Same approach will be used for Unit 2.

issue resolved in IR 390/93-1201)

• Draft Information for Illustration Only G. Arent 7

Regulatory Framework - Example 3* I" Approved License Basis - Supplemented by:Generic Communication 1982 SER SRP TITLE Approval for WBN Approval Guidance Additional Information Unit 2 Reference. (GL, Bulletins, other) 1

_ _ _ _ _ _Note _.._"

3.8.3 3:8.4 -Other Seismic Original 1982 SER B80-11 *B80-11 "Masonry Wall Design" -NRC accepted Category I Structures all but completion of corrective actions in IR50-390/93-01 and 50-391/93-01 (February 25, 1993) and closed for Unit 1 in IR50-390/95-46 (August 1, 1995) - Complete implementation for Unit 2.

• Draft Information for Illustration Only G. Arent 8

Regulatory Framework- Example 4*

Alternate Action for.Unit Two 1982 SER SRP TITLE Approval for WBN Approval Guidance Additional Information Unit 2 Reference (GL, Bulletins ,

other)

Note I 4.4 4.4 -Thermal and 4.4.8 - LC Detectors for SSER10- GL 82-28/NUREG In the original SER, the review of the ICC Hydraulic Design Inadequate core cooling October 1992 0737, lI.F.2 instrumentation was incomplete. The January 24, (1I.F.2) 1992 letter in response to GL 82-28/11.F.2 "inadequate Core Cooling Instrumentation System" superseded the previous responses on this issue. This letter addressed both WBN Units 1 and 2. NRC reviewed and approved for WBN Units 1 and 2 in SSER 10. WBN Unit 2 action -

Install Westinghouse ICCM-86 and associated hardware.

rne2 Tew* I bytf ior C

~

_________~~ ~ ~ ~

__________ ~ ~ ~ ~ ~

______________ ~ ~ ~ ~ ~~"~ y~5XXX b__________

• Draft Information for Illustration Only G. Arent 9

Regulatory Framework - CAP & SP Example*

Program Description References Unit 2 Status and TVA Commitment CAP - Cable Tray Supports CAP Plan and Closure: CAP is open (Design and Physical Deficiencies with cable trays and their TVA letter dated September 6, 1991, Modification) supports included inadequate tray WBN - Nuclear Performance Plan, connections, inconsistencies between as- Volume 4, Revision 1, Section 111.2.2, For Unit 2, the Unit 1 approach will be designed versus as-built tray Cable Tray and Cable Tray Supports used. Walkdowns will be performed to configurations and their orientation, and TVA letter dated October 20, 1995, Cable identify deviations from design documents; failure to evaluate all loading on cable tray Tray and Cable Tray Supports Corrective calculations will be developed for those members. Action Program Closure Report configurations that were not present on Unit 1, and acceptance criteria revised as The CAP for Unit 1 assured the structural appropriate, limits for acceptable adequacy and compliance with design configurations determined and drawings criteria and licensing requirements by: NRC Approval of Approach: revised to include these configurations;

" Review and revision of design criteria. Safety Evaluation of the WIB CAP Plan for and modifications made, as required.

" Review or development of design output Category I Cable Tray and Cable Tray requirements to comply with design Supports, September 13, 1989 criteria and to adequately translate TVA SSER 6, April 1991 design requirements. This included validation calculations for typical hardware config urations and critical cases.

• Walkdown of field configurations to identify deviations from design output.

• Modifications to field conditions, where necessary, to ensure that they are consistent with design output documents.

• Draft Information for Illustration Only G. Arent 10 1

Regulatory Framework -Closing Comments

" Provides the Unit Two Licensing Basis

" Based on the Staff Requirements Memorandum

>*-Unit One and Unit Two Licensing Basis Fidelity

• Addresses October 23rd Information Request

" Regulatory Framework Submittal - January 31, 2008 M. Bajestani 11

Regulatory Framework IM I QUEST IONS G. Arent 12

Scope of Watts Bar Nuclear Plant Unit 2 Licensing Review Identification of Topics for Additional Technical Review Unit 1 Licensing Basis Standard

1. Review topic (NUREG-0847section, NPP CAP or SP, generic issue, etc.)

yes .

13. In scope for

7. In scope to assessment against determine effect of applicable multiunit operations requirement ENCLOSURE 3